ML19253C740
| ML19253C740 | |
| Person / Time | |
|---|---|
| Issue date: | 08/11/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1656, NUDOCS 7912120058 | |
| Download: ML19253C740 (47) | |
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DATE ISSUED: 8/11/79 I
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MEETING MINUTES OF THE ACRS SUBC0411TTEE ON TMI-2: ACCIDENT BULLENTINS AND ORDERS JULY 9, 1979 WASHINGTON, D.C.
On July 9,1979, the ACRS Subcomittee on TMI-2: Accident Bulletins and Orders met in Washington, D.C., to discuss the response of vendors / utilities to the NRC Office of Inspection and Enforcement Bullentins and NRC Orders. The notice of this meeting appeared in the Federal Register on Friday, June 22, 1979. There were no requests for oral or written statements from menbers of the, public and none were made at the meeting.
Attachment A is the copy of the meeting agenda. The attendees list is Attachment B.
Attachment C is the tentative schedule for the meeting.
Selective slides and handouts from the meeting are Attachment D to these minutes. A complete set of slides and handouts is attached to the office copy of these minutes.
OPEN SESSION (8:35 am - 4:15 pm) INTRODUCTION Mr. Mathis, Subcomittee Chaiman, called the meeting to order at 8:35 a.m.
The Chairman explained the purpose of the meeting and the procedures for conducting the meeting, pointing out that Dr. Thome, G. McCreless was the Designated Federal Employee in attendance. The Chaiman introduced Dr. Denwood Ross (NRC Staff) to begin the day's presentations.
NRC BULLENTINS AND ORDERS TASK FORCE OVERVIEW - D. ROSS, NRC Dr. Ross, Leader of the TMI-2 Accident Bulletins and Orders (B&O) Task Force, gave an overview of the B&O Task Force activities. The B&O Task Force has two charges:
(1) review of the responses of all operating plants to the I&E bulletins, "h,,.
and (2) evaluate operating plant capabilities in such TMI-2 effected areas as:
l For
[.'
small break LOCA, auxiliary feed water systems, and operating procedures.
We 1537 089 F;
t-
- 9121 S C 06 C
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TMI-2 B&O July 9,1979 L
i (1) above, NRC will issue SERs following satisfactory responses from th utilities; for (2) above, the B&O Task Force will issue generic reports addressing the necessary h[, CE and GE plant requirements.
i The h[ report addressing the areas of small break IDCA, auxiliary feedeter and operating procedures is due to be received by the NRC on
- systems, (Note:
'Ihis report, WCAP-9600, has been sent to members of the B&O
, 1979.
committee.)
The B&O Task Force is primarily a short-term effort t
remaining beyond the expected life of the B&O Task Force (Dece b Any w rk will be factored into the work of the Lessons Learned Ta m er 1979)
Dr. Mattson.
orce under r
In response to a question from Mr. Mathis, Dr. Ross suggested an with the Subcommittee be held in mid-to-late August.
At that time, the NRC generic report addressing the necessary Westinghouse plant modifications required in the 3
areas of small break LOCA analysis, auxiliary feed systems, and p procedures will be issued.
The NRC report on CE plant requirements in these areas will be well along to completion at that time as well.
Dr. Shewmon asked how B&W piants would cope with the problem of n gases and the possible blockage of natural circulation.
Dr. Ross replied that the NRC Staff would address this question in a later presentation There was a brief discussion of the status of TMI-Unit 1.
The Commission has directed, by an order dated July 2,1979 (Attachment D-1), that Unit 1 remain shutdown pending Commission review of the restart application The Commission has also directed that a hearing be held prior to restart In response to a question from Mr. Etherington, Dr. Ross said he envisions a SER could be issued for Unit 1 restart within one month of receipt of Metropolitan Edison's response to the Commission's detailed concerns on Unit 1 restart.
1537 090
e e
TMI-2 B&O July 9, 1979 WESTINGHOUSE OWNER'S GROUP PRESENTATIONS - C. REED, V. ESPOSITO Mr. Reed, Chairman W Owner's Group, provided an overview of the organziation and cbjectives of the Owner's Group. S e Owner's Group consists of all eighteen operating utilities with W plants, plus Pacific Gas and Electric, which owns the Diablo Canyon plant.
We principal activities of the Owners's Group includes:
(1) perform generic analyses for the B&O and Lessons learned Task Forces, (2) perform generic analyses of ACRS consultant C. Michelson's concerns, and (3) review and developnent of guidelines for plant operating procedures.
S e generic analyses focused on the areas of small break LOCA behavior, natural circulation, and response of auxiliary feedwater systems.
Work in the procedures area involves review and revision of Westinghouse operating guidelines addressing the areas of immediate actions and diagnosis taken by an operator for such items as:
plant transient, IDCA, natural circulation, and others.
a Mr. Esposito gave an overview of the Westinghouse report on snall break accidents for W reactors (WCAP-9600). Se report is divided into five main topic areas. Rese areas are:
(1) small break method aspects; (2) small break general behavior; (3) specific scenario analyses; (4)
C. Michelson's concerns; and, (5) W reference emergency operating instruc-tions (Figures D2-3).
Westinghouse noted that the report consumed 11.4 engineering man-months, 31/2 months of technician time, and 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of CDC-7600 computer time.
Highlights of the Subcommittee questions during the above discussion includ following:
Dr. Shewmon asked if any W analyses show that the core is uncovered Mr. Esposito replied that the core is uncovered briefly for the 2 inch break The length of time that the core is uncovered is a function of:
(1)how soon the " loop seal" (length of oicing between the reactor coolant pumo an generator) is cleared of fluid, and (2) the time required for safety injection flow to match the break flow.
Mr. Esposito noted that these two conditions apply to a cold leg break.
For a hot leg break of this size (2 inches),
there is no core uncovery.
Mr. Esposito also noted that if one or all PROVs are open there is no core uncovery.
Dr. Shewmon asked if there is direct 1537 091 r
TMI-2 B&O
-4 July 9,1979 indication of MRV opening on Westinghouse plants.
Mr. Esposito replied that there are indicators to monitor the opening of the pilot stem valve of the MRV.
Dr. Ross (NRC) indicated that NRC has not yet decided whether pilot stem valve indicators ccxnplies with the Lessons Learned Task Force recommendations of " direct indication of opening" of the FORVs.
Mr. Esposito sunnarized his remarks and presented a set of conclusions (Figures D4-6). The ccnclusions support Westinghouse's contention that their NSSS design is safe.
In response to Subconnittee questions there was additional di the Westinghouse analysis of multiple failure accide t scussion of action at an early time in the transient (Figure D-7)n s requiring operator asked if two-phase flow throtxjh PORVs is a concern.Mr. Etherington the PORV at Davis-Besse did pass two-phase fluid and thDr. Ross noted th damaged.
e valve was not Dr. Ross noted however that it is not known how a POR perfonn given a waterhammer incident.
would WESTINGHOUSE REVISED REFERENCE EMERGEllCY OPERATING Mr. Zordan reviewed the need, objectives, philosophy, and process for Westinghouse's revision of their emergency operating instructions.
Mr. Zordan also noted that Westinghouse will also be reviewing, and revising a both their normal and abnormal operating instructions.
Mr. Zordan noted that Westinghouse uses the descriptive term instructions rather than procedures since the utilities use these instructions to develop their plant procedures after evaluation by the utility staff.
Mr. Etherington asked if, prior to Three Mile Island, Westinghouse reviewed the utility's procedures to insure compliance with the intent of the Westinghouse instructions. Mr. Zordan replied that, in general, they did not.
1537 092
- 3.., r
o TMI-2 B&O July 9,1979 Mr. Zordan noted the objectives of the Westinghouse revision of ope instructions are to assure:
(1) multi-instrument bases for operator actions, (2) completion of imediate actions necessary for safety prior to operator diagnosis of the transient, and (3) minimize differences in operator acti until diagnosis is complete and plant recovery is in progress.
The Westinghouse philosophy behind the reference operating instructions includes such provision for continuing diagnosis by the operator during the transient (1)
, (2) provision for detailed instructions and notes to the utilities, (3) the plan should be stabilized by automatic systems prior to the operator takina c and (41 if safety injection is tenninated. the operator must continue to c the plant manually.
Dr. Ross noted that the NRC will be reviewing the Westinghouse emergency operating instructions.
Mr. Zordan reviewed the process for developing these emergency instru (Figure D-8),as well as the structure of the emergency procedu An example of the emergency instructions was also described (Fig The emergency instructions are structured such that procedure E-0 con steps for verification of safety system operation, immediate operator action to be taken, and-finally diagnosis of the transient.
Transient diagnosis leads to procedures E-1 '(LOCA), E-2 (loss of secondary coolant), or generator tube rupture).
In response to a question from Mr. Etherington, Dr. Ross noted that the meeting between NRC/W is scheduled for July 1
,1979, to continue review of the Westinghouse operating instructions(Note:
I attended this meeting and have provided a report to the ACRS.)
COMBUSTION ENGINEERING 0WNER'S GROUP PRESENTATIO
, G. MENZEL Mr. Liebler briefly outlined the organization and objectives of the CE Ow G roup.
He noted that seven utilities comprise the Owner's Group and that the Owner's Group has been charged by utility management to assure th plants.
Mr. Liebler reviewed the schedule for submittal of their generic report to the NRC B&O Task Force (Figure D-14).
He noted that the analytical effort is well along, while the review of operator procedures is just CE will make a two-part submittal of infonnation; the first submittal to the 1537 093 r-
TMI-2 B&O July 9,1979 NRC will be on July 18, with the rest of the work being submitted by July 31 1979.
Problems areas noted by Mr. Menzel included the ever-present problen of limited resources necessitating this work on an generic basis, with the result that day-to-day generic analyses are being neglected.
Mr. Menzel detailed the CE Owner's Group effort in the area of small break LOCA analysis.
The basis for this work is a NRC information t equest consisting of sixteen separate items (Figure 0-15).
Most of the work falls under the titles of small break methods effort, and small break analysis effort.
Mr. Menzel detailed the work scope for the methods and a (Figures D16-18).
nalysis efforts He noted that the analysis effort will use Calvert Cliffs as the sample plant, with special cases run for plant areas that diff Calvert Cliffs.
er from In an earlier discussion of the PORV, it was reported that this valve survived two phase flow at Davis Besse. Dr. Shewmon asked if the CE PORVs are similar to B&W PORVs.
Mr. Thadani (NRC Staff) said that it was his understanding that the B&W and CE PORVs are the same, but that the W PORVs differ from the other two vendors' valves.
Mr. Menzel said completion of the analysis work will result in a more detailed understanding of small break behavior, particularly when significa energy removal is required via the steam generator.
NRC PRESENTATIONS - 8. SHERON, A. THADANI Mr. Sheron presented a brief discussion of the Staff's work on non-conde gases in response to questions from Dr. Shewmon earlier in the day.
Mr. Sheron showed estimates of non-condensible gas sources for B&W and CE pla D-19-20).
He noted that there is good agreement between the NRC versus CE estimate of gas sources.
1537 094
a TMI-2 B&O 7
July 9, 1979 fir. Sheron showed graphs of estimates of equilibrium non-condensible gas volumes, and non-condensible gas volume versus percent of core cladding reacted (Figures D21-22). Figure 21, shows that if all the non-condensible gas found its way to the hot leg-U-bends in the B&W plants, system pressure would have to drop below 400 psi in order to block natural circulation. It was also noted that if 10% of the core clad reacts the upper head plenum and hot leg U-bends will be filled with non-condensible gas. Mr. Sheron noted that the Staff has not yet 3
made a recommendation concerning the suggestion for remote venting on the high points of the, primary system. He also noted that the NRC believes for small i
break accidents that do not result in degraded core conditions, there is a wide margin to blockage of natural circulation by non-condensibles.
In I
response to a question from Dr. Shewmon, Mr. Sheron said that for the CE plants the worst location for non-condensible gases to gather is in the top of the U-tubes of the steam generators.
Mr. Sheron discussed the status of the NRC analysis tasks for the short-term (through January 1980). There are three subtasks involved here:
(1) analysis of small break LOCAs; (2) analysis of symptoms of inadequate core cooling /
required actions to restore core cooling; and, (3) analysis of transient and accident scenarios, including operator actions not previously analyzed. Details of these three subtasks were also described (Figures D-23-25).
The schedules of submittals for information from the W and CE Owner's Group was briefly discussed.
It was noted that NRC NUREG Reports on the W and CE plants short-term requirements are due to be issued the weeks of July 30, and August 19, 1979, res pecti vely.
In response to a question from Mr. Mathis, Dr. Rosztoczy (NRC), noted that to date there is no agreement between NRC and the Westinghouse and CE Owner's Group regarding the scope of subtasks 2 and 3 noted above.
Mr. Sheron briefly reviewed some results of NRC audit calculations of the
[
Westinghouse ECCS calculations.
1537 095 1
e TMI-2 B&O July 9,1979 Mr. Ashok Thadani discussed the generic NURH3 Reports that will be issued the B&O Task Force containing recerteendations for continued safe opera y
of Westinghouse and CE plants.
A copy of the proposed report topics is attached (Figure D-26).
We report is expected to contain both lorg-and short-term recommendations.
We NURU3 reports are due to be issued on the short-term recommendations by the end of August.
Mr. Thadani detailed the recommendations contained in the report.The recommendations fall into the followirig categories:
licensing, analysis, auxiliary feedwater system, ECCS, PORVs, containment isolation, natural circulation, operator considerations, and other instrumentation '(Figures D-27-31 ).
Both long-term and short-term recomendations were detailed under the various topics above.
In response to a question from Mr. Etherington, Mr. Thadani said that his definition of short-term implementation is on the order of three months.
Mr. Jack Heltemes discussed how the NRC proposes to implement the short-and long-term recommendations (Figure 0-32).
It is currently envisioned that the Westinghouse and CE generic reports will be issued around mid-August.
The short-term recomendations are expected to be completed, and a SER issued, b the B&O Task Force ceases to exist on December 1,1979.
The long-tenn recommendations would be fed into the work of the Lessons Learned T A final report of the Lessons Learned Task Force is due on September 1,1979.
The long-term recommendations are expected to be implemented through NRR via a letter from H. Denton.
Dr. Shewmon expressed concern that the utilities and vendors be allowed an opportunity to coment on the recommendations proposed by the Staff.
Mr. Novak assured the Subcommittee that there has been, and continues to be, dialog between the NRC Staff and the Industry on these recommendations.
1537 096
TMI-2 B&O July 9, 1979 OWNER'S GROUP COMMENTS ON NRC PRESENTATIONS - C. REED Speaking on behalf of the W and CE Oaner's Groups, Mr. Reed made the following comments:
(1) NRC should designate to the Industry, respnsi-bility for certain review areas of the NUREG reports.
In particular, the areas of control room layouts and operator training were sited. AIF currently has a Committee looking at these problems; (2) NRC should justify its requirements for the analyses requested. Bere is concern I
over the " battleship on the prairie" accident analysis syndrome requested t
by the NRC. Se Owner's Group suggested a meeting with the NRC Staff to discuss this item; (3) there seems to be little or ro interaction between the two NRC Task Forces. It was noted that interaction with the NRC Task Forces is a serious strain on the Owner's Group / vendor resources.
It was suggested a meeting with H. Denton, et. al., may be useful here.
The following comments were made by members of the Subcomittee. Mr. Mathis felt there was a need to upgrade maintenance training and procedures.
He also suggested that more productive use be made of simulator time and that he felt with little time and expense, control room instrumentation and layout could be significantly upgraded. Mr. Reed felt that whatever changes are made to control boards, the opinions of the oDerators should he factnrad into the process.
Dr. Shewman suggested that since the FAA licenses airplane mechanics, their ~ knowledge in this area may prove useful to the NRC in the upgrading of maintenance personnel.
Dr. Shewmon also said a lot of maintenance errors could be getting passed off as " instrument drift" or "cause unknown".
OPEN EXECUTIk-SESSION In an open r
_"tive session, the Subcomittee di. ;ussed its future meetina schedule, and s.ggested that Dr. Ross be contacted to obtain his recomendations concerning the interactions of the ACRS B&O and Lorig-Term Implications Subcommittees.
The Chairman also requested that at the next S> ccornittee meeting, the B&O 1537 097
a TMI-2 B&O July 9, 1979 Task Force discuss the genesis of bulletins and orders within the NRC order to provide the Subcommittee with a backdrop for evaluation of
, in Task Force effort.
Note,:
In further discussion of Dr. Ross, it was suggested that the B&O Subcommittee track the implementation of the NRC recommendatio while the ACRS Subcommittee following Dr. Mattson's Lessons Le Task F orce focus on the policy matters inherent ir, the NRC reco tions.
The meeting was adjourned at 4:30 p.m.
1537 098 NOTE:
A copy of a transcript of this meeting is available in the NRC Pu Document Room, at 1717 H St., N.W., or can be obtained from c
Reporters, 444 North Capital Street, N.W., Washington
- e eral
, D. C.
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Federal Regisier / Vol. 44. No.122 IFriday, June 22. 1979 / Notices 36526 Mown, and maintain a nuclear power ava' e for inspection or png in the Designated Federal Employee for this meeting. Dr. Thomas G. McCreless.
nt in a safe condition.ne the Co
- ssion's Public cument ulations also require operating Room at 1 - H Stree (telephone 202/634-3267) between 8.15 li seea to file annual financial re rts Washington.
.5.
a.m. and 5:00 p.m EDT.
Dated June M.19'9.
Dated at hasir en. D.C. this 15th day of rtified financial statements.
.se John C. Ho>la.
or req rements provide the NFC sts with Juneigg, nt information about a licen e's For the K. ar Regu ry Commissiod, Advisory Comr.ittee Management O'ficer.
p om -md &n. a a as al cu fina ial status,during the opera..g life g,,,,j
,,tg, se,,o coog 7:sw and c commissioning of a nuc!
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p g,,j, powe fant.
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- '""****"I De regoing partial denial oes not-CURITIES AND EXCHANGE t the Commission b reached mean a decis n on the need for ar ndments C
MISSION Advisory Committee on Reactor.
[R asa No. 21o96; 31-7701 to its re f ations to provide ion specific idance on decor
.issionin8 Safeguards. Ad Hoc Subcommittee on criteria f nuclear power ants. Nor the Three Mile Island, Unit 2, Accident lean Can Co.; App!! cation for does the ; rtial denial of
.e petition to Bulletins and Orders; Meeting Exe ption require a ty bonds n reclude the The ACRS Ad Ho'c Subcommittee on June. to's.
use of sure bonds. if become
- the Three M21e Is!and. Unit 2 Accident No 4 is Hereby Civen that the available a one of seve 1
Bu!!etins and Orders, will hold an open Ame n Can Company ("Ameri
').
decommisst
.ing finan al alternatives - meeting on July 9.1979 in Room ItMS.
a bold compan), has filed an In the future. t does m in that, based 1717 H St NW. Washington.DC 2055),
appli on for exemption pursu to on cunent '
matio e Commission has determin that i houldnot amend to consider the response of vendors /
' sectio is)(3)(A) and 3(a)(5)
.e its regulations req re bonding at this utilities to the NRC Office ofInspection Public L 5ty Holdmg Compen ct of time as specifi ily ggested by and Enforcement Bulletins and NRC 1935 ("A
"). Allinterested pe as are s anner the Orders.
referred t the apphcation w
. is petitioners. In Commission pr ic s a more timely In accordance with the procedure 8 summariz i below, for a de
,. tion of response to peti ers' request than outlined in the Federal Register on American ad its subsidiari 1nd a delaying action i il other potential October 4.19 8. (43 FR 45926), oral or statement to the basis u which an alternatis es can assessed. As was written statements may be presented by exemption requested.
announced in a
!eral Register notice members of the public, recordings will America.
New jerne rporation, on March 13.19
'3 FR 10370) the be permitted only during those portions is engaged ectly and.
agh its ntly engsged in a of the meeting when a transcript is being subsidiaries..dtrectly p.anly in the Commission is
.c e luation of its kept and questions may be asked only manufacture, istributic.nd sale of comprehensive practices relat.g t iecommissioning by members of the Subcommittee.its containers an packag-products and nuclear facili' es."I# detalled plan and consultants. and Sts'f. persons desiring consumer pro cts an
. resource schedule for evah3
- ion is described in to make oral statements should notify recovery and emic erstions. In an NRC sta eport <
titled. " Plan for the Designated Federal Employee as far 1978. America ndi bbsidiaries Reevaluatio of NR olicy on in advance as practicable so that reported net sa, c' 981.000 M t-A Decommiss >ning of. clear Facilities" appropriate arrangements can be made netincome of 5 5 000.
(NURE 6), dated tarch 1978, and to allow the necessary time during the One of Ameri subsidiaries is arathon Corpe n Canada Limited Revision 1 f that do
.ent, dated meeting for such statements.
December 978. One m 'or component The egenda for subject meeting shall M.Mara thon"). M
.nonm wholly g.
of this ov all reevalue,n is an be as follows:
owned by Ame
. except for extenelv xamination the financial Afonday July s. 379: ac30 o.m. Until the directors' quah!
shares. and is
-headquartered tario. Canada. it la assuranc needed to cov r Conclusion of Business t
through plants. is intended d this ite Subcommittee may meet in engaged direc a.
decomm sioning costs o utfear power anufacture and subsidiaries, r.e examin aon to assess the lauve Executive Session, with any ofits distribution
. ape. toducts.
merits several different ancial consultants who may be present, to American n of nada Limited explore and exchange thetr preliminary g.American c."), a.olly-owned assura e techniques, suc. s escrow opinions regarding matters which should Cmdian s :sidiary Marathon, ow'ns accou
- s. sinking fund acco nis, etc.,
be considered during the meeting and to and opers' manuf ac. -ing facilities in andt Seigh and judge the ancial a ssur ice needed in regard formulate a report and recommendation the Town Marathon, ntario.
deco mssioning the variou. lasses of to the full Committee.
Canada.
Its facilities, erican Ltd.
nucle r facilities.The Commi ion notes At the conclusion of the Executive g "
"fp.
that e petitioners may seek become Seesfon. the Subcommittee will hold 8,',",'
.'a ti t tr-to ds.
y a pa cipant in any subseque NRC dacussions with representatives of the m s: strid power is Id to rule. > king action on financin he costs NRC Staff. various utilities and Penin
.a Utilities Limited of d ommissioning and prese. the industries, and their consultanta.
g p,
,g ), also e Cana n erg ients made in their petitio pertinent to this review, subs.ary of Marathon, w
. is rega ling the need for and bene e of Further information regarding top!ca eng ed solely in the busine of sure y bonds or other alternatives such to be discussed.whether the meeting asing excess electrical wer from as use for escrow accounts or sinking has been cance!!ed or rescheduled, the rican Ltd. and distribu '
nd se as such power to commer Iand Chairman s ruling on requests for the funds.
Copies of the petition for rulemaking, opportunity to present oral statements ential customers in the Town of and the time allotted therefor can be athon. Peninsula does not sell the associated public comments, and the obtamed by a prepaid telephone call to al uical power in any other location.
Commission's letter to the petitioner are
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1537 099 ff//ac/xd' h
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SUBCOMMITTEE MEETING ON TMI-2:
ACCIDENTS BULLETINS & ORDERS WASHINGTON, DC JULY 9, 1979 ATTENDEES LIST _
ACRS P. O'Reilly W. Mathis, Chairman A. Thadani H. Etherington, Member B. Sheron P. Shewmon, Member J. Heltemes T. McCreless, Staff
- D. Ross P. Boehnert, Staff R. Audette
- Designated Federal Employee Z. Rosztoczy BALTIMORE GAS & ELEC. CO NUTECH T. Martin NUCLEAR ENGRG R. Olson FLORIDA POWER & LIGHT C0 E st F. Alligood T. Grozan J. Ahloada G. Liehler E. Baum COMBUSTION ENGINEERING OPPD Kruse c.
K. Morris P. Newton J. Westhoven EPRI G. Menzel FRAttATOME (FRANCE)
A.
d ntiades J. Amrouni NORTHEAST UTILITIES PRESIDENT'S COMMISSION ON R. Wells THE ACCIDENT AT TM1 E. Foster M. Mlynczak CAROLINA POWER & LIGHT W. Bland D. Water WESTINGHOUSE PACIFIC GAS & ELEC C0 R. Skwarek C. Blanc P.. fluench EDISON ELECTRIC INST.
R. Burch L., Mills J. Grady W. Gangloff PSE&G D. Maire R. Skwarek K. Huber J. Wroblewski V. Esposito T. Zordm EEI H. Kaczowka L. Mills J. 0"Cilka SCE&G_
ARKANSAS POWER & LIGHT C0 D. Dixon J. Enos R. Cook 1537 100 ATTACHMENT B
TitI-2 Mtg on B&O July 9, 1979 Cont'd Attendees List B&W OPS R. Borsum D. Aabye C0:4 EDIS0tl 0F flew YORK C0f45UMERS POWER C0 D. VandeWalle D. Speyer G. Cashell YAW;EE ATOMIC ELEC. C0 BECHTEL POWER CORP A. Husain B. Montgomery COMMO:; WEALTH EDIS0:1 DUKE POWER C0 C. Reed St Lewis ACE FEDERAL D. Hoffman D. Davis 1537 101
MEETIPG OF THE ACRS SUBCOMMITTEE ON MI-2:
ACCIDENT BULLETINS AND ORDERS JULY 9, 1979 WASHIFGTON, D.C.
TDRATIVE SCHEDULE OF PRESDRATIONS PRESDRATION ACTUAL TIME
- TIME EXECUTIVESES5kON 10 min 8:30 am I.
W. MATHIS - SUBCOMMITTEE CHAIRMAN II.
INTRODUCTION 5 min W. PATHIS III. OERVIEW OF NRC BULLETINS AND ORDERS (B&O) 15 min 9:00 am TASK EORCE e'
D. ROSS - NRC IV. hTSTItGHOUSE NJD COMBUSTION DGINEERIfC OWNER'S GROUP / VENDOR PRESENTATIONS A.
hTSTItGHOUSE PRESENTATION 60 min 9:30 am
- 1. C. Reed - W Owner's Group
- 2. V. Esposito - W_
BREAK 10 min 11:00 am B.
COMBUSTION DGINEERItG PRESDRATION 60 min 11:10 am
- 1. G. Liebler - CE Owner's Group
- 2. G. Menzel - CE WNCH 12:40 pn V.
NRC PRESDRATIONS A.
B&O GENERIC REPORT ON W AND CE PLANT 60 min 1:40 pn REQUIREMENTS 1.
REPORT OUTLINE A. THADANI 2.
SHORT TERM RECOMMENDATIONS A. THADANI
- AN ALLOWANCE, AMOUVTItG TO APPROXIMATELY 50-100% OF WE PRESENTATION TIME, HAS BEEN MADE FOR QUESTIONING BY THE SUBCOMMITTEE 1537 102 AYTAcMMSNT C
JULY 9,1979 'IMI-2
'IDUATIVE SCHEDULE OF PRESDRATIO1S
~
PRESDITATIQ1 ACTUAL
~
TIME TIFI*
3.
LOtG TERM RECOMMEt0ATIO1S A. THADANI NRC PLANS FOR RESOLUTIONS OF REQUIREMINTS 4.
J. HELTEMES 10 min 3:15 pn BREAK 30 min 3:40 pn GGER'S GROUP / VENDORS COMMENTS Of tRC GENERIC REPO V.
(IF ANY) 4:10 pn SUBCOMMITTEE DISCUSSION (OPEN EXECUTIVE SESSION)
VI.
5:00 pn VII. AIMOURN S
- AN ALIDANCE, AMOUNTING 'IU APPROXIMATELY 50-100% OF BEEN MADE FOR QUESTIONItG BY THE SUBCOMMITTEE 1537 103
UNITED STATES f'"f j NUCLEAR REGULATORY COMMISS!ON ll i
i g/
Office of Public Affairs 5g v.,**"*/
Washington, D.C. 20555 l
FOR IMMEDIATE RELEASE No.79-115 (Mailed - July 3, 1979)
Contact:
Frank L.
Ingram Tel.
301/492-7715 NOTE TO EDITORS Attached is a copy of a Nuclear Regulatory Commission 1 at the Three Mile
" Order" related to the status of Unit Unit I was Island Nuclear Power Station in Pennsylvania.
shutdown for refueling at the time of the March 28 accident at Unit 2 and has remained shutdown since that time.
f Attachment 1537 104 ATTACHMffD-l
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D Doexrrto USNRC UNITED STATES OF AMERICA (f.
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NUCLEAR REGULATORY COMMISSION g
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Offies of the Scac4 Do:ketw & ssmes E'#
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4 co In the Matter of
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METROPOLITAN EDISON COMPANY
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Docket No. 50-289
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Three Mile Island Nuclear
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Station, Unit No. 1
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ORDER at In view of the variety of issues raised by the accident the Three Mile Island Unit No. 2 facility, the Comission presently lacks the requisite reasonable a'ssurance that the same licensee's Three Mile Island Unit No. 1 facility, a nuclear power reactor of similar design, can be operated without endangering the health and safety of the public.
Accordingly, we direct that shall No.1 facility, presently in a shutdown condition, the Unit remain shut down until further order of the Commission itself.
The Commissien has further determined that it is in the public The a hearing precede restart of the facility.
interest that Commission will also issue an order within thirty (30) days 1537 105 specifying in detail the basis for its concerns, and the The procedures to severn further proceedings in this matter.
licensee may file a written answer to this Order no later than twenty (20) days after the i DUPLICATE DOCUMENT The Com.ission has foun Entire document previously and interest require that thi entered nto system under:
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